Use of PSA at Institute for Radiological Protection and Nuclear Safety for EPR licensing purposes
Congress title :PSAM - 9th International Conference on Probabilistic Safety Assessment and Management
Congress date :18/05/2008
The "Technical Guidelines for the design and construction of the next generation of NPPs with Pressurized Water Reactors" specify that the safety demonstration has to be achieved in a deterministic way, supplemented by probabilistic methods. Additionally it is specified that a PSA must be conducted, beginning at the design stage, including at least internal events. In general the probabilistic approach should be used in order to demonstrate a significant reduction of the global core melt frequency comparing with the existing NPPs. The accident situations which would lead to large early releases, such as V-LOCA, boron dilutions, high pressure core melting, spent fuel pool melting, etc. should be "practically eliminated". For EPR the PSA was used from the beginning of the design, several design improvement being defined. In the frame of the application for commissioning it is expected that EDF will provide an "as-build" full scope PSA for the reactor and for the spent fuel pool. The probabilistic approach will cover the internal events, the internal and external hazards of significant impact. In parallel, in order to dispose of the appropriate knowledge and tools for the independent verification of the EDF studies, IRSN develops its own limited scope PSA model.